Letter Sequence Request |
|---|
|
|
MONTHYEARML20049J9911982-03-19019 March 1982
Proposed Changes to Tech Specs 5.6 & 5.7 Re Spent Fuel Storage Rack Installation.Safety Evaluation Encl
Project stage: Request
ML20049J9891982-03-19019 March 1982
Application for Amend to Ol,Changing Tech Specs for High Density Spent Fuel Storage Rack Installation
Project stage: Request
ML20049J9931982-03-31031 March 1982
Spent Fuel Pool Mod
Project stage: Other
ML20054E1211982-04-21021 April 1982
Forwards Amend 1 to 820319 Spent Fuel Pool Mod,Incorporating Responses to Unit 2 Questions Identified in Encls 2,3 & 4 of NRC .Responses to Question 1 Were Addressed in
Project stage: Other
ML20054E1241982-04-30030 April 1982
To Spent Fuel Pool Mod
Project stage: Other
ML20065A4971982-09-0909 September 1982
Forwards Amend 2 to Spent Fuel Mod,In Response to NRC .Amend Also Corrects Minor Typographical Errors
Project stage: Other
ML20027B3321982-09-14014 September 1982
Forwards Corrected Page IV-12 to Spent Fuel Pool Mod Amend 2,changing Typographical Errors in Load Combinations Column of Stress Interactions Table for 7x8 Rack
Project stage: Other
ML20073S4901983-04-15015 April 1983
Eia Supporting Amend 31 to License NPF-2
Project stage: Other
ML20073S4801983-04-15015 April 1983
Amend 31 to License NPF-2,revising Tech Specs to Increase Storage Capacity of Spent Fuel Pool from 675 to 1,407 Storage Locations
Project stage: Other
ML20073S4911983-04-15015 April 1983
Notice of Issuance & Availability of Amend 31 to License NPF-2
Project stage: Other
1982-04-30
[Table View] |
|
|---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B1791999-10-0404 October 1999
Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions
ML20196J8731999-06-30030 June 1999
Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation
ML20209B8161999-06-30030 June 1999
Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS
ML20207D6421999-05-31031 May 1999
Proposed Conversion to ITSs for Chapter 3.3
ML20206H0001999-04-30030 April 1999
Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS
ML20206F4421999-04-30030 April 1999
Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8
ML20206B4721999-04-21021 April 1999
Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F
ML20205G8571999-04-0202 April 1999
Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90
ML20205A2401999-03-19019 March 1999
Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation
ML20207C2451999-02-22022 February 1999
Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details
ML20203A7711999-02-0303 February 1999
Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4
ML20196F6261998-12-0101 December 1998
Proposed Tech Specs Pages Re Amend to Licenses NPF-2 & NPF-8.Proposed TS Changes Include Revisions to SG Level Setpoints,Rcs Operational Leakage & Specific Activity Limits & SG Tube Insp Program
ML20196B6241998-11-20020 November 1998
Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0
ML20155J4561998-11-0606 November 1998
Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement
ML20154K2521998-10-12012 October 1998
Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety
ML20237D4111998-08-20020 August 1998
Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations
ML20217N4801998-05-0101 May 1998
Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs
ML20217Q7261998-03-20020 March 1998
Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a
ML20202G1311998-02-12012 February 1998
Proposed Tech Specs Re Pressure Temp Limits Rept
ML20202F1121998-02-12012 February 1998
Revised Proposed Changes to TS Page 6-19a for Power Uprate
ML20198H3661998-01-0707 January 1998
Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied
ML20198E6621997-12-31031 December 1997
Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value
ML20198E3141997-12-30030 December 1997
Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances
ML20197B6691997-12-18018 December 1997
Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept
ML20211P5861997-10-16016 October 1997
Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F
ML20211J1501997-09-30030 September 1997
Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept
ML20217C0341997-09-25025 September 1997
Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage
ML20211A6891997-09-17017 September 1997
Proposed Tech Specs Re Primary Coolant Specific Activity
ML20216D0031997-09-0303 September 1997
Proposed Tech Specs Re Moveable Incore Detector Sys
ML20149K1001997-07-23023 July 1997
Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits
ML20148R7521997-06-30030 June 1997
Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis
ML20148Q1041997-06-30030 June 1997
Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec
ML20148K7501997-06-13013 June 1997
Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement)
ML20140A3931997-05-28028 May 1997
Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis
ML20148E5921997-05-27027 May 1997
Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves
ML20148F2381997-05-27027 May 1997
Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends
ML20138B9251997-04-23023 April 1997
Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing
ML20137H6091997-03-25025 March 1997
Proposed Tech Specs Re Primary Coolant Specific Activity
ML20136F8231997-03-0707 March 1997
Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements
ML20135C4941997-02-24024 February 1997
Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend
ML20135C6731997-02-24024 February 1997
Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems
ML20135C8641997-02-14014 February 1997
Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power
ML20134J4051997-02-0606 February 1997
Proposed Tech Specs,Providing Addl Info Re voltage-based Repair Criteria for SG Tubing
ML20133G5801997-01-10010 January 1997
Proposed Tech Specs Re Generic Laser Weld Sleeving & Deleting One Cycle Implementation of L* Which Expired at Last Unit 2 Outage
ML20138G9581996-12-26026 December 1996
Proposed Tech Specs Reflecting Guidance Contained in GL 95-05, SG Tube Support Plate Voltage-Based Repair Criteria, Using Revised Accident Leakage Limit of 20 Gpm & Using Probability of Detection That Is Voltage Dependent
ML20134N9211996-11-18018 November 1996
Proposed Tech Specs Bases B 3/4 2-5 Re RCS Total Flow Rate Surveillance
ML20134K5551996-11-15015 November 1996
Proposed Tech Specs 3.6.2.2 Re Spray Additive Sys
ML20134G9601996-11-11011 November 1996
Proposed Tech Specs Amending License NPF-8 to Replace Farley Specific Laser Welded Sleeve Requirements Currently in TS W/Generic Laser Welded Sleeve Process
ML20149L8991996-11-0606 November 1996
Revised Technical Specification Pages for Plant Units 1 & 2
ML20128M4821996-10-0808 October 1996
Proposed Tech Specs Reflecting Deletion of Cycle Specific L* Repair Criteria Which Expires at Start of Next Unit 2 Refueling Outage
1999-06-30
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999
Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions
ML20209B8161999-06-30030 June 1999
Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS
ML20196J8731999-06-30030 June 1999
Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation
ML20207D6421999-05-31031 May 1999
Proposed Conversion to ITSs for Chapter 3.3
ML20206H0001999-04-30030 April 1999
Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS
ML20206F4421999-04-30030 April 1999
Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8
ML20206B4721999-04-21021 April 1999
Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F
L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999
Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with
ML20205S9641999-04-20020 April 1999
Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with
ML20205G8571999-04-0202 April 1999
Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90
ML20205A2401999-03-19019 March 1999
Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation
ML20205A3101999-02-28028 February 1999
Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program
ML20207C2451999-02-22022 February 1999
Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details
ML20203A7711999-02-0303 February 1999
Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4
ML20205T0011998-12-23023 December 1998
Rev 17 to FNP-0-M-011, Odcm
ML20205T0081998-12-23023 December 1998
Rev 18 to FNP-0-M-011, Odcm
ML20196F6261998-12-0101 December 1998
Proposed Tech Specs Pages Re Amend to Licenses NPF-2 & NPF-8.Proposed TS Changes Include Revisions to SG Level Setpoints,Rcs Operational Leakage & Specific Activity Limits & SG Tube Insp Program
ML20196B6241998-11-20020 November 1998
Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0
ML20155J4561998-11-0606 November 1998
Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement
ML20154K2521998-10-12012 October 1998
Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety
ML20151V6991998-09-11011 September 1998
Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with
ML20237D4111998-08-20020 August 1998
Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations
ML20217N4801998-05-0101 May 1998
Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs
ML20205S9971998-04-19019 April 1998
Rev 16 to FNP-0-M-011, Odcm
ML20217Q7261998-03-20020 March 1998
Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a
ML20202F1121998-02-12012 February 1998
Revised Proposed Changes to TS Page 6-19a for Power Uprate
ML20202G1311998-02-12012 February 1998
Proposed Tech Specs Re Pressure Temp Limits Rept
ML20198H3661998-01-0707 January 1998
Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied
ML20198E6621997-12-31031 December 1997
Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value
ML20198E3141997-12-30030 December 1997
Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances
ML20197B6691997-12-18018 December 1997
Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept
ML20212B1791997-10-31031 October 1997
1 SG ARC Analyses in Support of Full Cycle Operation
ML20211P5861997-10-16016 October 1997
Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F
ML20211J1501997-09-30030 September 1997
Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept
ML20217C0341997-09-25025 September 1997
Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage
ML20211A6891997-09-17017 September 1997
Proposed Tech Specs Re Primary Coolant Specific Activity
ML20216D0031997-09-0303 September 1997
Proposed Tech Specs Re Moveable Incore Detector Sys
ML20149K1001997-07-23023 July 1997
Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits
ML20148Q1041997-06-30030 June 1997
Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec
ML20148R7521997-06-30030 June 1997
Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis
ML20148K7501997-06-13013 June 1997
Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement)
ML20140A3931997-05-28028 May 1997
Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis
ML20148F2381997-05-27027 May 1997
Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends
ML20148E5921997-05-27027 May 1997
Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves
ML20138B9251997-04-23023 April 1997
Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing
ML20198T4921997-03-31031 March 1997
Small Bobbin Probe (0.640) Qualification Test Rept
ML20137H6091997-03-25025 March 1997
Proposed Tech Specs Re Primary Coolant Specific Activity
ML20136F8231997-03-0707 March 1997
Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements
ML20135C4941997-02-24024 February 1997
Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend
ML20135C6731997-02-24024 February 1997
Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems
1999-06-30
[Table view] |
Text
..
ATTACHMENT 1 DESIGN FEATURES' 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
AKeff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes conservative allowances for uncer-tainties and biases based on a maximum enrichment of 4.3 weight percent U-235.
b.
A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that Keff will 'not exceed 0.98, based on maximum enrichment of 3.5 weight percent U-235, assuming aqueous foam moderation.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.
CAPACITY 5.6.3 The spent fuel storage pool is designcd and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.
I 5.7 COMP 0NENT CYCLIC OR TRAMSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
I i
f FARLEY - UNIT 1 5-7 8203290300 spo3,9 l
DR ADDCK 05000348 PDR
[
ATTACHMENT 2 SAFETY EVALUATION FOR FARLEY UNIT 1 SPENT FUEL P00L MODIFICATION
Background:
The spent fuel pool at Farley Unit 1 currently contains 13-inch center-to-center spent fuel storage racks. The current spent fuel storage capacity of Unit 1 is 675 fuel assemblies. Alabama Power Company plans to install high density poison spent fuel storage racks at Unit 1.
The installation.
of these racks will increase the capacity of the Unit 1 spent fuel pool to 1407 fuel assemblies and require a' revision to the plant technical specifications.
References:
(1) Farley - Unit 1 Technical Specification 5.6.
(2) Joseph M. Farley Nuclear Plant Final Safety Analysis Report.
(3) NRC letter to All Power Reactor Licensees, dated April 14, 1978.
(4) NRC letter to All Power Reactor Licensees, dated January 18, 1979.
(5) Joseph M. Farley Unit 1 Spent Fuel Pool Modification Report.
Bases:
The attached report entitled " Joseph M. Farley Nuclear Plant Unit 1 Spent Fuel Pool Modification" provides the bases for the proposed expansion of the spent fuel pool. lne information provi,ded in this report is consistent with the NRC guidance paper for spent fuel pool modification applications transmitted in References 3 and 4.
The report documents the compliance of the Farley - Unit I high density poison spent fuel rack installation with the NRC requirements as specified in the position paper referenced above.
The proposed technical specification revisions are provided in Section III l
of this report.
The technical specification revisions were associated with Section 6.6 on Fuel Storage.
Paragraphs 5.6.1.1.a and 5.6.1.1.b were revised to incorporate the maximum enrichment and nominal center-to-center distance between fuel assemblies placed in the storage racks.respectively.
Paragraph 5.6.1.2 has been deieted because the first core loading has taken place and Alabama Poser Company does not intend to place new fuel in these racks under dry conditioss.
New fuel may be stored in these racks under wet or flooded conditions.
Paragraph 5.6.1.3 has been revised to indicate the maximcm enrichment for the new fuel racks. Additionally, paragraph 5.6.1.3 has been renumbered to 5.6.1.2.
l i
t
r
.=
Paragraph 5.6.3.has been revised to increase the capacity of the spent fuel pool from 675 to 1407 fuel assemblies. The bases for the above changes are documented in Reference (5).
1
==
Conclusion:==
f The proposed expansion of the spent fuel pool and change to Section 5.6 of the technical specifications do not involve an unreviewed safety question 3
as defined by 10CFR50.59.
4 i
I
's e
i
AllACHMENT l
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